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Insp Rept 50-482/86-05 During Mar 1986.Violation Noted: Performance of Control Room Emergency Ventilation Sys Train B Operability Test Not Documented According to Procedure
	ML20197E685
Person / Time
Site:	Wolf Creek
Issue date:	05/01/1986
From:	Bruce Bartlett, Cummins J, Hunter D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20197E630	List: ML20197E626; ML20197E648; ML20197E685;
References
	50-482-86-05, 50-482-86-5, NUDOCS 8605150298
	Download: ML20197E685 (8)
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APPEtiDIX B

U.S. NUCLEAR REGULATORY C0tHISSION

REGION IV

NRC Inspection Report: 50-482/86-05 LP: NPF-42

Docket: 50-482

Licensee: Kansas Gas and Electric Company (KG&E)

Post Office Box 208 .

Wichita, Kansas 67201

Facility Name: Wolf Creek Generating Station (WCGS)

Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas

Inspection Conducted: March 1-31, 1986

Inspectors: bl -l

J. I. IUmmins, Sen'ior Rbsident Inspector, Operations Date

tilb i e

B. L. Bartlett, Residel[t' Reactor Inspector, Date

Operations

Approved: b i

D. R. Hunter, Chief, Project Section B, Reactor Uate

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Projects Branch

Inspection Summary

Inspection Conducted March 1-31, 1986 (Report 50-482/86-05)

Areas Inspected: Routine, unannounced inspection including followup on

previously identified NRC items, operational safety verification, engineered

safety features system walkdown, onsite followup of events, monthly

surveillance observation, monthly maintenance observation, and plant tours.

Results: Within the seven areas inspected, one violation was identified

(failure to document the performance of a surveillance test in accordance with

procedure, paragraph 6). One open item is identified in paragraph 5.

8605150298 860507

PDR

G ADOCK 05000482

PDR:

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DETAILS

1. Persons Contacted

Principal Licensee Personnel

J. A. Bailey, Interim Site Director

F. T. Rhodes, Plant Manager

M. Estes, Superintendent of Operations

M. D. Rich, Superintendent of Maintenance

M. G. Williams, Superintendent of Regulatory, Quality, and

Administrative Services

0. L. Maynard, Manager, Licensing

J. Goode, Licensing

K. Peterson, Licensing

G. Pendergrass, Licensing

W. M. Lindsay, Supervisor, Quality Systems

C. E. Parry, Superintendent-Quality Systems Engineering

C. J. Hoch, QA Technologist

R. D. Flannigan, Supervisor, Compliance Engineering

A. A. Freitag, Manager, Nuclear Plant Engineering-WCGS

C. M. Herbst, Project Engineer, Bechtel

M. Megehee, Compliance Engineer

W. J. Rudolph, QA Manager

The NRC inspectors also contacted other members of the licensee's staff

during the inspection period to discuss identified issues.

Denotes those personnel in attendance at the exit meeting held on

April 2, 1986.

2. Followup on Previously Identified NRC Items

(Closed) Violation (50-482/EA85-127-A and 50-482/8535-01): Violation

Of Technical Specification-Centrifugal Charging Pump (CCP) Inoperable.

The violation involved a failure to restore CCP '1A' to operable status

within the time limit of the action statement for Technical Specifica-

tion 3.5.2. The NRC inspector reviewed the licensee's response and veri-

fied that changes have been made to STS BG-100A and STS BG-1008 to correct

ambiguous statements; that Licensee Event Report (LER) 85-063-00 was placed

in the operations required reading and was signed off as being read by the

appropriate shift personnel; that shift supervisors were trained in post-

test review requirements; and by walkdowns of selected engineered safety

features (ESF) systems that Technical Specification requirements were

being met. This violation is closed.

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(Closed) Violation (50-482/EA85-127-B and 50-482/8535-02): Failure to

Observe Protective Clothing Requirements Of a Radiation Work Permit.

The violation involved a radiation worker entering a radiologically

controlled work area without donning the required protective clothing.

The NRC inspector verified that this event was documented in accordance

with Procedure ADM 03-006, " Notice of Radiological Work Practice

Violation," and that the station operator was counseled on the

importance of complying with RWP procedures. This violation is closed.

(Closed) Violation (50-482/EA85-127-C and 50-482/8535-03): Violation

Of Technical Specification-Containment Fire Detection Instrumentation

Out-0f-Service.

The violation involved failure to establish a fire watch or monitor

containment air temperature in accordance with Technical Specifica-

tion 3.3.3.8 when the fire detection instrument for Fire Detection

Zone 201 was inoperable. The NRC inspector verified that Procedure

ADM 02-010, " Shift Relief and Turnover," and LER 85-070-00 were assigned

and read as required reading. In addition, the NRC inspector, through

interviews with licensed operators, ve.ified that oncoming crew members

were cognizant of plant equipment status prior to assuming shift duties.

This violation is closed.

(Closed) Violation (50-482/EA85-127-0 and 50-482/8535-04): Failure To

Follow Installation Criteria For Various Conduits.

The violation involved using an unapproved method to install a flexible

conduit. The NRC inspector reviewed the management letter that was sent to

all station employees. Field _ inspections by the NRC inspector of

selected items revealed no other violations of this type. This item is

closed.

(Closed) Violation (50-482/8537-01): Nonseismic Glass Level Gauge Not

Isolated.

The violation involved a failure to isolate a seismic portion of a

safety-related system from a nonseismic portion. The NRC inspector

verified that Checklist (CKL) EG-120 had been revised to show the four

valves locked closed; that the five additional tanks that were-

identified each had their appropriate checklist revised; that Procedure

ADM 02-102, " Cont.01 of Locked Component Status," had been revised to

show proper positioning; and through field inspection verified that the

appropriate valves were closed and locked. This item is closed.

No violations or deviations were identified.

3. Operational Safety Verification

The NRC inspectors verified that the facility was being operated safely

and in conformance with regulatory requirements by direct observation

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of licensee facilities, tours of the facility, interviews and discussions

with licensee personnel, independent verification of safety system status

and limiting conditions for operations, and by reviewing facility records.

The NRC inspectors, by observation, interview of personnel, and review of

documents, verified the physical security plan was being implemented in

accordance with the security plan and that radiation protection activities

were controlled.

By observing valve position, electrical breaker position, and control

room indication, the NRC inspectors confirmed the operability of the

accumulator safety injection system and the coolant charging system.

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The NRC inspectors also visually inspected safety components for leakage,

physical damage, and any other impairment that could prevent them from

performing their designed function.

No violations or deviations were identified.

4. Engineered Safety Features (ESF) System Walkdown

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The NRC inspectors verified the operability of ESF systems by walking

down selected accessible portions of the systems. The NRC inspectors

verified valves and electrical circuit breakers were in the required

position, power was available, and valves were locked where required.

The NRC inspectors also inspected system components for damage or other

conditions that could degrade system performance.

The ESF systems listed below were walked down during this inspection

report period:

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Refueling Water Storage (BN)

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High Pressure Coolant Injection (EM)

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Emergency Fuel Oil (JE)

No violations or deviations were identified.

5. Onsite Followup of Events

The NRC inspectors performed onsite followup of nonemergency events that

occurred during this report period. The NRC inspectors (when available)

observed control room personnel response, observed instrumentation

indicators of reactor plant parameters, reviewed logs and computer

printouts, and discussed the event with cognizant personnel. The NRC

inspectors verified the licensee had responded to the event in accordance

with procedures and had notified the NRC and other agencies as required in

a timely fashion.

Engineered Safety Feature actuations that occurred during the report

, period are listed in the table below. Where applicable, the NRC

inspector will review the LER for each of these events and will report

any findings in subsequent NRC inspection reports.

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1

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Date Event * Plant Status Cause

3/26/86 CRVIS Mode 1 Blown Fuse on

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Chlorine Detector

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3/27/86 CRVIS, CPIS,

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& FBVIS Mode 1 Failed Power Supply

? 3/27/86 AFW, Actuation

With LSP Switch-

1 over to ESW Mode 1 Personnel Error

Event

i CRVIS - control room ventilation isolation signal.

CPIS - containment purge isolation signal

FBVIS - fuel building ventilation isolation signal

AFW - auxiliary feed water

. LSP - low suction pressure

ESW - essential service water

Selected NRC inspector observations:

On March 27, 1986, at 1813 hours0.021 days 0.504 hours 0.003 weeks 6.898465e-4 months a CRVIS, CPIS, and FBVIS were generated

when the -15 volt DC power supply failed in Cabinet SA 036D. After

approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of reviewing prints, the instrumentation and control

(I&C) personnel trouble shooting the problem removed a fuse in a 120V AC

circuit and when it was replaced, an AFW actuation occurred along with an

AFW low suction pressure automatic switchover to ESW. As designed, only

the '1A' train ESW pump started. The balance of plant (80P) operator

shut down the three running AFW pumps before any ESW water was placed in

the steam generators (S/Gs).

Operations personnel flushed the ESW water out of '1A' motor driven AFW

pump and the turbine driven AFW pumps (TDAFWP) using 1-inch drain lines and

gravity feed from the condensate storage tank (CST). After chemistry

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samples taken from the AFW system and analyzed indicated the system was

again clean, the AFW pumps were run in their normal modes supplying water

to the S/Gs to ensure all ESW water was flushed from the AFW system.

Currently an evaluation is in progress to determine the corrective action

required to ensure that the' long term operation of the AFW system has not

been degraded through chemical reactions to the ESW water. The NRC

inspector will follow up this evaluation to verify proper corrective

action has been taken. Using Work Request (WR) 01336-86, I&C replaced the

failed power supply on March 28, 1986. This will be tracked as Open Item

No. 50-482/8605-02.

No violations or deviations were identified.

6. Monthly Surveillance Observation

The NRC inspectors observed selected portions of the performance of.

surveillance testing and/or reviewed completed surveillance test procedures

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to verify that surveillance activities were performed in accordance with

TS requirements and administrative procedures. The NRC inspectors

considered the following items while inspecting survePlance activities:

- Testing was being accomplished by qualified personnel in accordance

with an approved procedure.

- The surveillance procedure conformed to TS requirements.

- Required test instrumentation was calibrated.

- Technical Specification limiting conditions for operation (LCO) were

satisfied.

- Test data was accurate and complete. Where appropriate, the NRC

inspectors performed independent calculations of selected test data

to verify their accuracy.

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The performance of the surveillance procedure conformed to applicable

administrative procedures.

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The surveillance was performed within the required frequency and the

test results met the required limits.

Surveillances witnessed and/or reviewed by the NRC inspectors are listed below:

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STS IC-920, Revision 4, " Containment Hydrogen Analyzer GS 065A

Calibration Test"

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STS EJ-100A, Revision 0, "RHR System Inservice Pump '1A' Test"

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STS GK-001B, Revision 5, " Control Room Emergency Ventilation System"

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STS IC-913, Revision 4, " Containment Hydrogen Analyzer GS 065B

Calibration Test"

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STS88-004, Revision 4, "RCS Water Inventory Balance"

Selected NRC inspector observations:

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On March 26, 1986, the NRC inspector observed a portion of the

performance of STS GK-001B and then reviewed the surveillance proce-

dure. During this review, the NRC inspector observed that even though

the surveillance had been in progress for a number of hours, Section 3,

" Initial Conditions," had not been signed off as completed. When the

supervising operator was informed, he stated, that when the previous

shift had started the surveillance, they had missed signoff of this

section. This failure to document the performance of a Section 3 of

the surveillance in accordance with procedure is an apparent violation

(50-482/8605-01).

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7. Monthly Maintenance Observation

The NRC inspector observed maintenance activities performed on

safety related systems and components to verify that these activities

were conducted in accordance with approved procedures, Technical

3 Specifications, and applicable _ industry codes and standards. The following

elements were considered by the NRC inspector during the observation and/or

review of the maintenance activities:

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LCO were met and, where applicable, redundant components were

operable.

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Activities complied with adequate administrative controls.

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Where required, adequate, approved, and up-to-date procedures were

used. ,

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Craftsmen were qualified to accomplish the designated task and

technical expertise (i.e., engineering, health physics, operations)

were made available when appropriate.

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Replacement parts and materials being used were properly certified.

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Required radiological controls were implemented.

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Fire prevention controls were implemented where appropriate.

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Required alignments and surveillances to verify post maintenance

operability were performed.

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Quality control hold points and/or checklists were used when

appropriate and quality control personnel observed designated work

activities.

Selected portions of the maintenance activities accomplished on the work

requests (WR) listed below were observed and related documentation reviewed

by the NRC inspector:

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WR 01305-86, "BB FB-426A, Replace NAll Card"

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WR 01112-86, " Containment Hydrogen Analyzer GS 065A, Zero Reading Is

Off Scale"

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WR 01336-86, "SA 036D, -15 Volt DC Power Available Light Not- l

Illuminated, All Red Train Process Monitor Bistables Tripped" l

No violations or deviations were identified.

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8. Plant Tours

At various times during the course of the inspection period, the NRC

inspectors conducted general tours of the reactor building, auxiliary

building, radwaste building, fuel handling building, control building,

turbine building, and the secured area surrounding the buildings. During

the tours, the NRC inspectors observed housekeeping practices, fire

protection barriers and equipment, and maintenance on equipment. The NRC

inspectors also discussed various subjects with licensee personnel.

No vialations or deviations were identified.

9. Open Items

Open items are matters which have been discussed with the licensee, which

will be reviewed further by the inspector, and which involve some action

on the part of the NRC or licensee or both. An open item disclosed during

the inspection is discussed in paragraph 5.

10. Exit Meeting

The NRC inspectors met with licensee personnel to discuss the scope and

findings of this inspection on April 2, 1986. The NRC inspectors also

attended entrance / exit meeting with another NRC region-based inspector

identified below:

Inspection Lead Area Inspection

Period Inspector Inspected Report No.

3/10-14/86 C. Hackney Emergency 86-06

Preparedness

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ML20197E685

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